ML19210B133
| ML19210B133 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/16/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210B132 | List: |
| References | |
| NUDOCS 7911040067 | |
| Download: ML19210B133 (5) | |
Text
.,
UNITED STATES
/
'o m' CLEAR REGULATORY COMMISslON y
'i nasmucTom. o. c. rosss i
e METRODOLITAN EDISON C09 ANY JiRSEY CEN]RAL POWEc AN: LIGHT C09 AV PENNSYLV ANIa ELECTRIC COMPANY DOCKET NO. 50-201 THREE MILE ISL AND NUCLE AR ST ATION, UNIT PC.1 G LICENSE
_AMENOMENT TO FACILITY OPERATIN Amencment Nc. 26 License No. OPR-50 The Nuclear Regulatory Commission (the Comr.ission) has foun 1.
that:
The application for amendment by Metropolitar Edison Company, Jersey Central Power & Light Company and(the licen A.
Pennsylvania Electric Companycomplies with the standards and March 9, 1977, requirements of the Atomic Energy Act of 1954, a regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with theap B.
and regulations of the Comission; There is reasonable assurance (i) that the act C.
endangering the health and safety of the pub with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and D.
safety of the public; and The issuance of this amendment is in accordanc Part 51 of the Commission's regulations and all applicable E.
requirements have been satisfied.
lJoo 264 40 % 7 79110
-2 Accordingly, the license is amended by chances to the Technical Specifications as indicated in the attachment to this lic 2.
No. DPR-50 is hereby amended to read as follows:
(2) Technical Soecifications_
The Technical Specifications contained in Appendices
, are A and B, as revised through Amendment No.
The licensee hereby incorporated in the license.
shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its 3.
issuance.
FOR THE NUCLEAR REGULAY COMMISSION h.!' ll*.
/
~e Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 16,1977 1586 2o5 B
9
ATTACHMENT TO LICENSE AWENDMENT NO.26_
FACILITY OPERATING LICENSE NO. OPR-50
_DOCXET NO. 50-289 Remove pages 3-3 and 3-4 fron the Appendix A Technical Specifications The changed and insert the attached revised pages 3-3 and 3.4 areas on the revised pages are shown by marginal lines.
1506 2 0
w
=
3.1.2 PRESSURIZATION, HFATUP, AND COOLDOWN I, IMITATIONS Applicability Applies to pressurization, heatup, and cooldown of the reactor coolant system.
Objective To assure that temperature and pressure changes in the re4ctor coolant system do not cause cyclic loads in excess of design for reactor coolant system components.
Specification 3.1.2.1 For the first two effective full power years (EFPY) the reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Figure 3.1-1 and Figure 3.1-2 and are as follows:
Heatup:
Allowable combinations of pressure and temperature shall be to the right of and below the limit line in Figure 3.1-1.
Heatup rates shall not exceed those shown on Figure 3.1-1.
Cooldown:
Allowable combinations of pressure and temperature for a specific cooldown shall be to the left of and below the limit line in Figure 3.1-2.
Cooldown rates shall not exceed those shown on Figure 3.1-2.
Hydro Tests:
For isothermal system hydrotests during the first two years of operations, the system may be pressurized to the limits set forth in specification 2.2, when there are fuel assemblies in the vessel and to ASME Code Section III limits when no fuel assemblies are present if the system temperature is 2150F or greater. The system may be tested to a pressure of 1150 psig provided system temperature is 175 F or greater.
Initial system hydrotests prior to criticality 0
may be conducted if the reactor coolant system temperature is ll8 F or greater.
3.1.2.2 The secondary side of the steam generator shall not be pressurized above 200 psig if the temperature of the steam generator shell is below 1000F, 3.1.2.3 The pressurizer heatup and cooldown rates shall not exceed 1000F in any one hour. The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 430F.
3.1.2.4 Within two effective full power ' rears of operation, Figure 3.1-1 and 3.1-2 shall be updated in accordance with criteria acceptable to the NRC.
Bases All reactor coolant system components are designed to. withstand the effects of cyclic loads due to system temperature and pressure changes.(1}
These cyclic b
Amendment No. J[. 26 3-3
D**D D
' 3 hf A
_ow oJ-
.1 s
loads are introduced by unit load transients, reacter trips, and unit heatup and cooldown operations. The nurber of thermal and loading cycles used for design The maximum unit heatup and cooldown purposes are shown in Table 4-8 of the FSAR.
l rate of 100 F in any one hour satisfies stress limits for cyclic operation.(2) 0 The 200 psig pressure limit for the secondary side of the steam generator at a terperature 2 e s s t ha:- I W satisfies stress levels for tamparatures below the DM.(3I The reactor vessel plate material and welds have been tost *J w ver A ry conformity to specified requirements and a maximum NDM value of 304 has been determined based on Charpy V-notch tests. The maximum NDTT value obtained for the steam generator shell material and welds was 40 F.
The heatup and cooldown rate limits in this specification are not intended to instantaneous rates of temperature change, but are intended to limit tempera-limit ture changes such that there exists no one hour interval, in which a temperature change greater than the limit takes place.
Figures 3.1-1 and 3.1-2 contain the limiting reactor coolant system pressure-temperature relationship for operation at DM(4) and below to assure that stress levels are low enough to preclude brittle fracture. These stress levels and their bases are defined in Paragraph 4.3.3 of the FSAR.
As a re,sult of fast neutren irradiation in the region of the core, there will be an increase in the NDW with accumulated nuclear operation. The predicted = v4 mum NDTT increase for the 40-year exposure is shown on Figure 4-10.(4)
The actual shift in NDU will be determined periodically during plant operation b testing
) The of irradiated vessel material samples located in this reactor vessel.(
results of the irradiated sanple testing will be evaluated and compared to the design curve (Figure 4-11 of the FSAR) being used to predict the increase in transition temperature.
The desi n value for fast neutron (E > 1 MeV) exposure of the reactor vessel is 3.1 x 10 0 n/cm2 see at the reference design power of 2568 MWt and an integrated e::posure of 3.0 x 1019 n/cm2 for 40 years operation. (6) The calculated maximum 2
2 19 n/cm integrat3d exposure for 40 values are 2.2 x 1010 n/cm see and 2.2 x 10 years operation at 80 percent load.(4)
Figure 3.1-1 is based on the design value which is considerably higher than the calculated value. The NDTT value for Figure 3.1-1 is based on the projected NDM at the end of the first two effective full power years of operation.
I I
The actual shift in ND M will be established periodically during plant operation by testing vessel material samples which are irradiated by securing them periodically near the inside wall of the vessel in the core area to achieve an average effective exposure between 1 and 3 times that of the reactor vessel inner surface.
To compensate for the increases in the ND M caused by irradiation, the limits on the pressure-temperature relationship are periodically changed to stay within the established stress limits during heatup and cooldown.
The NDM shft and the magnitude of the thermal and pressure stresses are sensitive to integrated reactor power and not to instantaneous power level. Figures.3.1-1 and 3.1-2 are applicable to reactor core thermal ratings up to 2568 MWt.
3-4 Amendment No.
26 2o8
.